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2. 发明公开

EP3076398A4 NUCLEAR FUEL PELLET HAVING ENHANCED THERMAL CONDUCTIVITY, AND PREPARATION METHOD THEREOF 审中-公开
标题翻译： KERNBRENNSTOFFTABLETTEN MIT VERBESSERTERWÄRMELEITFÄHIGKEITUND HERSTELLUNGSVERFAHRENDAFÜR
公开(公告)号：EP3076398A4
公开(公告)日：2017-06-21
申请号：EP14865710
申请日：2014-11-21
申请人： JOINT STOCK COMPANY AKME-ENGINEERING
发明人： KURINA IRINA SEMYONOVNA , POPOV VJACHESLAV VASILYEVICH , RUMYANTSEV VLADIMIR NIKOLAEVICH , RUSANOV ALEKSANDER EVGENIEVICH , ROGOV STEPAN SERGEEVICH , SHARIKPULOV SAID MIRFAISOVICH
IPC分类号： G21C3/04 , G21C3/58 , G21C3/62
CPC分类号： G21C3/623 , G21C3/044 , G21C3/58 , G21C21/02 , G21C2003/045 , Y02E30/38
摘要： The invention relates to nuclear physics, and specifically to reactor fuel elements and units thereof, and particularly to the composition of solid ceramic fuel elements based on uranium dioxide, intended for and exhibiting characteristics for being used in variously purposed nuclear reactors. The result consists in a more reliable, special structure and a simple composition of uranium dioxide without heterogeneous fuel pellet additives, approaching the characteristics of a monocrystal having enhanced, and specifically exceeding reference data, thermal conductivity as temperature increases, and a simple production method thereof. The result is achieved in that pores of between 1 and 5 microns in size are distributed along the perimeters of grains in the micro-structure of each metal cluster in a nuclear fuel pellet, and in that located within the grains are pores which are predominantly nano-sized. In addition, the metal clusters comprise between 0.01 and 1.0 percent by mass. The invention provides for a method of preparing a nuclear fuel pellet, including precipitating metal hydroxides, in two stages, having different pH levels. Uranium metal is melted at a temperature exceeding 1150°C, sintering is carried out in an insignificant amount of liquid phase at a temperature ranging between 1600 and 2200°C in a hydrogen medium until forming uranium dioxide, the structure of which includes metal clusters dispersed therein. An X-ray photon spectroscope is used for identifying the new structure of the UO2 pellet and the additional U-U chemical bond.
摘要翻译：本发明涉及核物理学，具体涉及反应堆燃料元件及其单元，并且具体涉及基于二氧化铀的固体陶瓷燃料元件的组合物，旨在用于并表现出用于各种目的的核反应堆的特征。其结果是具有更可靠，特殊的结构和二氧化铀的简单组成，没有非均质燃料颗粒添加剂，接近单晶的特性已经提高，特别是超过参考数据，随着温度升高导热率，以及其简单的生产方法。其结果得以实现，其尺寸在1至5微米之间的孔隙沿着核燃料芯块中每个金属簇的微观结构中的晶粒的周边分布，并且位于晶粒内的是主要为纳米尺度的。另外，金属团簇包含0.01-1.0质量％。本发明提供了一种制备核燃料芯块的方法，该方法包括两步沉淀金属氢氧化物，具有不同的pH值。铀金属在超过1150℃的温度下熔化，在氢气介质中在1600和2200℃之间的温度范围内，在不明显量的液相中进行烧结，直至形成二氧化铀，其结构包括分散的金属团簇在其中。 X射线光子分光镜用于识别UO2颗粒的新结构和额外的U-U化学键。

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